ML17319B303

Forwards Request for Addl Info Re Seismic Qualification of Auxiliary Feedwater Sys,Needed to Complete Review of Util Response to Generic Ltr 81-14

ML17319B303
Person / Time
Site:	Cook
Issue date:	04/05/1982
From:	Varga S Office of Nuclear Reactor Regulation
To:	Dolan J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
References
GL-81-14, NUDOCS 8204270007
Download: ML17319B303 (5)

Text

APR 5 1982 Docket Hos.60-315 and 60-316 ter. John Dolan,, Vice President Indiana and Michigan Electric Company Post Office Box 18, Bowling Green Station New York, Hew York 10004 DISTRI BUTIOV, Docket File<

NRC PDR Local PDR ORB 1 File D. Eisenhut OELD OI8IE (1)

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SUBJECT:

tlULTIPLANTACTION C-14, SEISMIC QUALIFICATIOH OF AUXILIARY FEEDMATER SYSTEM -

DONALD C.

COOK NUCLEAR PLANT UNITS 1

AND 2 lje have reviewed your response to NRC Generic Letter 81-14, which was issued

- under the provisions of 10 CFR 50.64(f).

The additional information identified in the Enclosure is required to complete our review.

The NRR Operating Plan requires that this multiplant action be completed by September 30, 1982.

Please supply the requested information within 30 days of the date of this letter.

The reporting and/or recordkeeping requirements contained in this letter are approved under OHB clearance 93150-0065 which expires 5/31/83.

Sincerely.

Enclosure:

Request for Additional Information cc w/enclosure:

See next page Steven A. Varga, Chief Operating Reactors Branch Ho.

1 Division of Licensing 88049VO DO7 ORB 1

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OFFICES SURNAME1I'ATE f

NRC FORM 318 OO-80) NRCM 0240

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OFFIC!AL RECORD COPY USOPO: 1981~9-960

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I Mr. John Dolan Indiana and Michigan Electric Company CC:

Mr. Robert W. Jurgensen Chief'Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire

-Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.

Washington, D. C.

20036 1

Maude Preston.Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 W.

G. Smith, Jr., Plant Manager Donald C. Cook Nuclear Plant P. 0.

Box 458 Bridgman, Michigan 49106 U. S.'uclear Regulatory Commission Resident Inspectors Office 770 Red Arrow Highway Stevensville, Michigan 49127 William J. Scanlon, Esquire 2034 Pauline Boulevard Ann Arbor, Michigan 48103 The Honorable Tom Corcoran United States House of Representatives Washington, D. C.

20515 James G. Keppler Regional Administrator - Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

ENCLOSURE Donald C. Cook bhcleaz Plant Units 1 h 2 SEISMIC QJALIFICATIOM OF THE AUXILIARYFEEDNATER SYSTEM REQUEST FCR ADDITIONAL INFORMATION Question 1:

Enclosure 1 of Gen ric Letter 81-14 (GL.81-14) defines the auxiliary feedwater (AFN) system to be considered as:

(a)

"The AFH system boundary from suction to discharge (including t¹ water source and heat sink) shall include those portions of the system required to accomplish the AFH system function and cdnnected branch piping up to and I

including the second valve which is normally closed'r.

capable of automatic closure when the safety function is S

required.Et

$b)

"The AFH system boundary shaD also include any portion of branch piping that:is structyrally coupled to the AFW system bound-ry such that the seismic response of the branch piping transmits loads to the AFH system.

As a minimum, this incluoes the branch lines outside the AFH I

system boundary'to a point of three orthogonal restraints."

(c)

"Allmechanical and electrical equipment, piping (e.g.,

instrument air), conduits and cable trays, which are necessary or con~n items which are necessary for the operation qf the AFK system, shall also be considered."

(d)

"In addition, the'tructures housing these systems and components shall be included."

Clarify the extent to which your AFN system boundary, considered in your August 28, 1981 response letter, coincides, with the boundary defined in GL 81-14, especially parts {a) and {b) above.

QuestXon 2:

Clarify why IE Bulletin 79-04 is not applicable to your. AFM system.

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